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Book/Report | FZJ-2016-05141 |
1986
Kernforschungsanlage Jülich GmbH, Zentralbiliothek, Verlag
Jülich
Please use a persistent id in citations: http://hdl.handle.net/2128/12470
Report No.: Juel-2064
Abstract: This paper describes and evaluates the data and results currently available on the storage of spent AVR fuel elements. Water basin and dry storage facilities as well as the extensive experimental and development work are taken into consideration. Only slight quantities of krypton 85 and tritium can be released from the fuel element. These isotopes are produced due to the uranium contamination of the graphite matrix resulting from manufacture. The first barrier is the coating of the nuclear fuel particles which retains practically all the fission products. The second barrier required for long-time storage is the welded fuel element can. Unlike existing casks in the FRG made of nodular graphite cast iron, a new AVR cask has been developed which is formed of mild steel R St 37-2 and a special heavy concrete. The cask does not have a leak-tightness function but rather only the function of shielding an mechanical protecting the two cans. It possesses the test and quality features of the type B(U) shipping cask pursuant to the IAEA Guidelines. The manufacturing costs are low so that a storage of 15 years involves costs to the amount of 35 DM/fuel element. A comparison of the AVR cask with the spent fuel disposal container for LWR-fuel element shows that it can be used for the direct disposal of spent AVR fuel elements. The cost estimate for spent fuel disposal in the year 2000 results in a value of 25 DM/fuel elements. Costs of 0.8 - 0.9 Dpf/kWh are calculated for the complete disposal of AVR fuel elements.
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